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| & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 tsrausch@pplweb.com SEP 3 0 2010 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP 1 - 17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION NOTICE OF DEVIATION FROM BWIP GUIDELINES Docket Nos. 50-387 PLA-6553 and 50-388 PPL Susquehanna, LLC is providing a Notification of Deviation from the Boiling Water Reactor Vessel and Internals Project Guidelines in accordance with BWRVIP-94, Revision 1. The deviation described on the attached is for BWRVIP-84, "Guidelines for Selection and Use of Materials for Repairs to BWR Internal Components" and BWRVIP- 18 1, "Steam Dryer Repair Design Criteria" guidance on weld material. | | & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 tsrausch@pplweb.com SEP 3 0 2010 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP 1 - 17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION NOTICE OF DEVIATION FROM BWIP GUIDELINES Docket Nos. 50-387 PLA-6553 and 50-388 PPL Susquehanna, LLC is providing a Notification of Deviation from the Boiling Water Reactor Vessel and Internals Project Guidelines in accordance with BWRVIP-94, Revision 1. The deviation described on the attached is for BWRVIP-84, "Guidelines for Selection and Use of Materials for Repairs to BWR Internal Components" and BWRVIP- 18 1, "Steam Dryer Repair Design Criteria" guidance on weld material. |
| This notification is provided for information only and no NRC action is being required. | | This notification is provided for information only and no NRC action is being required. |
| No regulatory commitments are contained in this letter. Should you have any questions, please contact Cornelius T. Coddington at (610) 774-401 | | No regulatory commitments are contained in this letter. Should you have any questions, please contact Cornelius T. Coddington at (610) 774-401 |
| : 9. Sincerely, Attachment Copy: NRC Regional I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. R. R. Janati, DEP/BRP Mr. B. Vaidya, NRC Project Manager Attachment to PLA-6553 Page 1 of 1 Description of Deviation from Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines The BWRVIP program implementation guidelines provide guidance to ensure the consistent application of BWRVIP guidelines by member utilities. | | : 9. Sincerely, Attachment Copy: NRC Regional I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. R. R. Janati, DEP/BRP Mr. B. Vaidya, NRC Project Manager Attachment to PLA-6553 Page 1 of 1 Description of Deviation from Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines The BWRVIP program implementation guidelines provide guidance to ensure the consistent application of BWRVIP guidelines by member utilities. |
| When Susquehanna, LLC does not implement any portion of an applicable "mandatory" or "needed" BWRVIP guideline that has been approved by the BWRVIP Executive Committee, we will notify the NRC and BWRVIP within 45 days following our approval of the deviation. | | When Susquehanna, LLC does not implement any portion of an applicable "mandatory" or "needed" BWRVIP guideline that has been approved by the BWRVIP Executive Committee, we will notify the NRC and BWRVIP within 45 days following our approval of the deviation. |
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Category:Letter type:PLA
MONTHYEARPLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums PLA-8048, Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence2023-01-14014 January 2023 Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence PLA-8042, Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence2023-01-10010 January 2023 Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence PLA-8039, Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information2022-12-22022 December 2022 Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information PLA-8038, Notification of Petition for Bankruptcy (PLA-8038)2022-12-14014 December 2022 Notification of Petition for Bankruptcy (PLA-8038) PLA-8036, Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-80362022-11-30030 November 2022 Registration for the Use of Spent Fuel Storage Casks 203, 202, and 204, PLA-8036 PLA-8035, Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-80352022-11-0808 November 2022 Registration for the Use of Spent Fuel Storage Casks 205, 200, and 201, PLA-8035 PLA-8031, Emergency Plan Revision 66 (PLA-8031)2022-11-0707 November 2022 Emergency Plan Revision 66 (PLA-8031) PLA-8032, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032)2022-10-28028 October 2022 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments - Supplemental Information (PLA-8032) PLA-8026, Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026)2022-10-19019 October 2022 Biennial 10 Crf 50.59 and 72.48 Summary Report and Changes to Regulatory Commitment (PLA-8026) PLA-8015, Application for Order Approving Indirect Transfer of Control of Licenses2022-09-29029 September 2022 Application for Order Approving Indirect Transfer of Control of Licenses PLA-8030, Evacuation Time Estimate Report PLA-80302022-09-15015 September 2022 Evacuation Time Estimate Report PLA-8030 PLA-8025, Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value2022-08-10010 August 2022 Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value PLA-8019, Nd Refueling Outage Owner'S Activity Report, PLA-80192022-07-13013 July 2022 Nd Refueling Outage Owner'S Activity Report, PLA-8019 PLA-8013, Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-80132022-06-27027 June 2022 Response to Request for Additional Information Regarding License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-8013 PLA-8012, 10 CFR 50.46 Annual Report2022-06-10010 June 2022 10 CFR 50.46 Annual Report PLA-8005, Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005)2022-05-23023 May 2022 Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005) PLA-8001, Radiation Exposure Information and Reporting System - PLA-80012022-04-28028 April 2022 Radiation Exposure Information and Reporting System - PLA-8001 PLA-7986, 2021 Annual Environmental Operating Report (Nonradiological) Docket No. 50-387, PLA-79862022-04-26026 April 2022 2021 Annual Environmental Operating Report (Nonradiological) Docket No. 50-387, PLA-7986 PLA-7987, Radioactive Effluent Release Report and Offsite Dose Calculation Manual - (PLA-7987)2022-04-26026 April 2022 Radioactive Effluent Release Report and Offsite Dose Calculation Manual - (PLA-7987) PLA-7985, Annual Radiological Environmental Operating Report2022-04-22022 April 2022 Annual Radiological Environmental Operating Report PLA-7883, Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883)2022-03-31031 March 2022 Proposed Amendment to Licenses NPF-14 and NPF-22: Relocate Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program (PLA-7883) PLA-7995, Property Insurance Program (PLA-7995)2022-03-30030 March 2022 Property Insurance Program (PLA-7995) PLA-7998, Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report2022-03-29029 March 2022 Submittal of Unit 1 Cycle 23 Core Operating Limits Report and Reload Safety Analysis Report PLA-7991, Proof of Financial Protection and Guarantee of Payment of Deferred Premium2022-03-24024 March 2022 Proof of Financial Protection and Guarantee of Payment of Deferred Premium PLA-7984, Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 22022-03-0808 March 2022 Supplement to License Amendment Requesting Adoption of TSTF-505, Revision 2 PLA-7962, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-79622022-01-0505 January 2022 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR PLA-7962 2024-01-04
[Table view] |
Text
Timothy S. Rausch Sr. Vice President
& Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 tsrausch@pplweb.com SEP 3 0 2010 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP 1 - 17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION NOTICE OF DEVIATION FROM BWIP GUIDELINES Docket Nos. 50-387 PLA-6553 and 50-388 PPL Susquehanna, LLC is providing a Notification of Deviation from the Boiling Water Reactor Vessel and Internals Project Guidelines in accordance with BWRVIP-94, Revision 1. The deviation described on the attached is for BWRVIP-84, "Guidelines for Selection and Use of Materials for Repairs to BWR Internal Components" and BWRVIP- 18 1, "Steam Dryer Repair Design Criteria" guidance on weld material.
This notification is provided for information only and no NRC action is being required.
No regulatory commitments are contained in this letter. Should you have any questions, please contact Cornelius T. Coddington at (610) 774-401
- 9. Sincerely, Attachment Copy: NRC Regional I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. R. R. Janati, DEP/BRP Mr. B. Vaidya, NRC Project Manager Attachment to PLA-6553 Page 1 of 1 Description of Deviation from Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines The BWRVIP program implementation guidelines provide guidance to ensure the consistent application of BWRVIP guidelines by member utilities.
When Susquehanna, LLC does not implement any portion of an applicable "mandatory" or "needed" BWRVIP guideline that has been approved by the BWRVIP Executive Committee, we will notify the NRC and BWRVIP within 45 days following our approval of the deviation.
BWRVIP- 1 8 1 deviation is detailed as a deviation from "needed" guidelines.
BWRVIP Document BWRVIP-84, "Guidelines for Selection and Use of Materials for Repairs to BWR Internal Components" and B WRVIP- 1 8 1, "Steam Dryer Repair Design Criteria" BWRVIP Requirement All welds between XM-19 components are to be made with EIER209 weld material.
Exception The steam dryer lifting eye and lug bolts (set screws) were fabricated from XM- 19 high strength stainless steel; however, the tack welds between the lift lug and lift bolt were fabricated and repaired using ER3 16L weld material.
Alternative In Lieu Of The ER3 16L weld material will be used in lieu of the ElER209 weld material because these tack welds function to prevent rotation of the lift lug bolts and there is no structural loading on these tack welds.